Thermomechanical analysis of tungsten-copper joints for fusion applications using digital image correlation

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-07-31 DOI:10.1016/j.fusengdes.2024.114608

Younes Belrhiti , Cory Hamelin , David Knowles , Mahmoud Mostafavi

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Abstract

The European DEMOnstration Fusion Power Plant DEMO represents a significant milestone in the progression towards sustainable fusion energy and a critical phase between ITER and commercial fusion reactors, aiming to demonstrate sustained net positive electricity production. Thanks to its properties, tungsten is a promising material for divertor armor. Coupled with copper alloys as heatsinks, they offer robust thermal management properties to deal with intense thermomechanical loads and irradiation damage. Understanding the thermomechanical behaviour of tungsten-copper joints during their application is then necessary for divertor design.

This study presents experimental analysis on tungsten-copper brazed materials subjected to thermomechanical solicitations to simulate mono-block conditions with heat fluxes expected to reach 20 MW/m² and so to face potential creep-fatigue failure. The experimental tests were coupled with Digital Image Correlation up to 400 °C to analyse the thermomechanical behaviour of these joints, providing insights into their thermal behaviour, structural integrity, damage accumulation, joint failure and identification of strains required for creep-fatigue assessment using design codes.

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利用数字图像相关性对钨-铜接头进行热力学分析以实现融合应用

欧洲 DEMO 聚变发电站 DEMO 是迈向可持续聚变能源的一个重要里程碑，也是国际热核试验反应堆和商业聚变反应堆之间的一个关键阶段，其目标是展示持续的净正发电量。由于钨的特性，它是一种很有前途的岔道铠装材料。与铜合金一起作为散热片，它们具有强大的热管理特性，可应对强烈的热机械负荷和辐照损伤。因此，了解钨-铜接头在应用过程中的热机械性能对于改向器的设计非常必要。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.